EP2859556B1 - Dampferzeuger für einen kernreaktor - Google Patents
Dampferzeuger für einen kernreaktor Download PDFInfo
- Publication number
- EP2859556B1 EP2859556B1 EP13777696.9A EP13777696A EP2859556B1 EP 2859556 B1 EP2859556 B1 EP 2859556B1 EP 13777696 A EP13777696 A EP 13777696A EP 2859556 B1 EP2859556 B1 EP 2859556B1
- Authority
- EP
- European Patent Office
- Prior art keywords
- plenums
- plane
- steam generator
- nuclear reactor
- perforations
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
- 239000002826 coolant Substances 0.000 claims description 29
- 239000012530 fluid Substances 0.000 claims description 21
- 238000000034 method Methods 0.000 claims description 12
- 230000008878 coupling Effects 0.000 claims description 10
- 238000010168 coupling process Methods 0.000 claims description 10
- 238000005859 coupling reaction Methods 0.000 claims description 10
- 230000008016 vaporization Effects 0.000 claims description 10
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 5
- 238000006243 chemical reaction Methods 0.000 description 4
- -1 uranium hydrides Chemical class 0.000 description 3
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 2
- 229910052770 Uranium Inorganic materials 0.000 description 2
- 238000009835 boiling Methods 0.000 description 2
- 229910052796 boron Inorganic materials 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 239000000446 fuel Substances 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 238000009834 vaporization Methods 0.000 description 2
- 229910052692 Dysprosium Inorganic materials 0.000 description 1
- 229910052691 Erbium Inorganic materials 0.000 description 1
- 229910052693 Europium Inorganic materials 0.000 description 1
- 229910052688 Gadolinium Inorganic materials 0.000 description 1
- 229910052772 Samarium Inorganic materials 0.000 description 1
- BQCADISMDOOEFD-UHFFFAOYSA-N Silver Chemical compound [Ag] BQCADISMDOOEFD-UHFFFAOYSA-N 0.000 description 1
- WZECUPJJEIXUKY-UHFFFAOYSA-N [O-2].[O-2].[O-2].[U+6] Chemical class [O-2].[O-2].[O-2].[U+6] WZECUPJJEIXUKY-UHFFFAOYSA-N 0.000 description 1
- 239000000654 additive Substances 0.000 description 1
- 230000000996 additive effect Effects 0.000 description 1
- 229910045601 alloy Inorganic materials 0.000 description 1
- 239000000956 alloy Substances 0.000 description 1
- 238000004458 analytical method Methods 0.000 description 1
- 229910052793 cadmium Inorganic materials 0.000 description 1
- BDOSMKKIYDKNTQ-UHFFFAOYSA-N cadmium atom Chemical compound [Cd] BDOSMKKIYDKNTQ-UHFFFAOYSA-N 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 229910017052 cobalt Inorganic materials 0.000 description 1
- 239000010941 cobalt Substances 0.000 description 1
- GUTLYIVDDKVIGB-UHFFFAOYSA-N cobalt atom Chemical compound [Co] GUTLYIVDDKVIGB-UHFFFAOYSA-N 0.000 description 1
- 150000001875 compounds Chemical class 0.000 description 1
- 238000009833 condensation Methods 0.000 description 1
- 230000005494 condensation Effects 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- KBQHZAAAGSGFKK-UHFFFAOYSA-N dysprosium atom Chemical compound [Dy] KBQHZAAAGSGFKK-UHFFFAOYSA-N 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- UYAHIZSMUZPPFV-UHFFFAOYSA-N erbium Chemical compound [Er] UYAHIZSMUZPPFV-UHFFFAOYSA-N 0.000 description 1
- OGPBJKLSAFTDLK-UHFFFAOYSA-N europium atom Chemical compound [Eu] OGPBJKLSAFTDLK-UHFFFAOYSA-N 0.000 description 1
- 238000011156 evaluation Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- UIWYJDYFSGRHKR-UHFFFAOYSA-N gadolinium atom Chemical compound [Gd] UIWYJDYFSGRHKR-UHFFFAOYSA-N 0.000 description 1
- 229910052735 hafnium Inorganic materials 0.000 description 1
- VBJZVLUMGGDVMO-UHFFFAOYSA-N hafnium atom Chemical compound [Hf] VBJZVLUMGGDVMO-UHFFFAOYSA-N 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 229910052738 indium Inorganic materials 0.000 description 1
- APFVFJFRJDLVQX-UHFFFAOYSA-N indium atom Chemical compound [In] APFVFJFRJDLVQX-UHFFFAOYSA-N 0.000 description 1
- 238000011835 investigation Methods 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 230000007246 mechanism Effects 0.000 description 1
- 239000011824 nuclear material Substances 0.000 description 1
- 230000010355 oscillation Effects 0.000 description 1
- 238000005381 potential energy Methods 0.000 description 1
- 230000008569 process Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- KZUNJOHGWZRPMI-UHFFFAOYSA-N samarium atom Chemical compound [Sm] KZUNJOHGWZRPMI-UHFFFAOYSA-N 0.000 description 1
- 229910052709 silver Inorganic materials 0.000 description 1
- 239000004332 silver Substances 0.000 description 1
- 230000000087 stabilizing effect Effects 0.000 description 1
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/16—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants comprising means for separating liquid and steam
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B1/00—Methods of steam generation characterised by form of heating method
- F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
- F22B1/16—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being hot liquid or hot vapour, e.g. waste liquid, waste vapour
- F22B1/162—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being hot liquid or hot vapour, e.g. waste liquid, waste vapour in combination with a nuclear installation
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/14—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from headers; from joints in ducts
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/006—Details of nuclear power plant primary side of steam generators
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
- G21C1/322—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core wherein the heat exchanger is disposed above the core
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Definitions
- a core of nuclear material is confined to a small volume internal to the reactor so that a reaction may occur.
- a controlled nuclear reaction may persist for an extended period of time, such as several years, before refueling of the reactor core is required. Accordingly, when used as a source of heat for converting water into steam, a properly designed nuclear reactor may provide a carbon-free, stable, and highly reliable source of energy.
- a nuclear reactor may make use of a working fluid, such as water, which may be converted to steam at a pressure significantly above atmospheric pressure.
- the pressurized steam may then be used to drive a turbine for converting mechanical energy to electric current.
- the steam may then be condensed back into water, and returned to the reactor.
- the cycle of vaporization, condensation, and vaporization of the working fluid may continue day after day and year after year.
- a significant feature of a nuclear reactor may be a steam generator that receives liquid coolant at an input side, vaporizes the coolant by way of exposure to the heat source of the nuclear reactor, and provides the vaporized coolant to the input of a turbine. Accordingly, the efficiency, ease of manufacture, performance, and the safety features of the steam generator represent areas of continued investigation, analysis, and evaluation. Nuclear reactors are disclosed in US 4,124,064 , CA 2 796 439 A1 and CA 2 796 487 A1 .
- a steam generator for a nuclear reactor comprises three or more plenums proximate with a first plane, wherein the first plane intersects a bottom portion of a column of a reactor vessel.
- the steam generator comprises three or more plenums proximate with a second plane, approximately parallel with the first plane, wherein the second plane intersects a top portion of the column.
- the steam generator further includes plurality of steam-generating tubes from a flowpath that conveys coolant from one of the three or more plenums located proximate with the first plane to at least one of the three or more plenums proximate with the second plane.
- a top portion of a steam generator includes three or more plenums disposed in a plane at approximately 90-degree intervals around a riser column, wherein at least one plenum of the three or more plenums includes an approximately flat tubesheet that faces a bottom portion of the steam generator, and wherein the approximately flat tubesheet of the at least one plenum includes a plurality of perforations, wherein the plurality of perforations changes in density between an area near an inner edge of the at least one plenum and an area near an outer edge of the at least one plenum.
- a method of operating a nuclear reactor includes conveying a working fluid from a first group of three or more plenums to a plurality of flowpaths, vaporizing the working fluid in at least some of the plurality of flowpaths, wherein the vaporizing results, at least in part, from coupling thermal energy from a reactor coolant to the at least some of the plurality of flowpaths.
- the method further includes transferring the vaporized coolant to a second group of three or more plenums.
- a group of plenums may be arranged in a first plane at 90-degree increments around a bottom portion of an approximately cylindrical riser column of a nuclear reactor.
- a second group of plenums wherein the second group may include four plenums, may be arranged in a second plane at 90-degree increments around a top portion of a cylindrical column of a nuclear reactor.
- Plenums located at both the top and bottom portions of the cylindrical riser column may include a substantially or approximately flat tubesheet having perforations that permit coupling to one of the plurality of steam generator tubes.
- an orifice may be disposed within with at least some perforations of the plenums located proximate with the bottom portion of the cylindrical riser column. The presence of an orifice may result, at least in part, in a decrease in pressure as fluid flows upward from the plenum at the bottom portion of the riser.
- three plenums may be arranged in a first plane at 120-degree around a bottom portion of an approximately cylindrical riser column of a nuclear reactor.
- a second group of plenums, wherein the second group may include three plenums, may be arranged in a second plane at 120-degrees around a top portion of a cylindrical riser column of a nuclear reactor.
- Plenums located at both the top and bottom portions of the cylindrical riser column may include substantially or approximately flat tubesheets having perforations that permit coupling to one or more of the plurality of steam generator tubes that form a flowpath between plenums located at the bottom and top portions of the cylindrical riser column.
- an orifice may be disposed within at least some perforations of the plenums located proximate with the bottom portion of the cylindrical riser column. The presence of an orifice may result, at least in part, in a decrease in pressure as fluid flows upward from the plenum at the bottom portion of the riser.
- perforations in one or more of the approximately flat tubesheets of the plenums are lower in density (for example, fewer in number per unit of area of the tubesheet) near an edge of the plenums closer to the cylindrical riser column and be of higher density (for example, greater in number per unit of area) nearby an outer wall of the reactor vessel enclosing the steam generator.
- Such a change in density of the perforations in the approximately flat tubesheet may result in an approximately uniform coupling of heat from a primary fluid within the reactor vessel to a secondary, working fluid within the steam generator tubes.
- embodiments of the invention may include various nuclear reactor technologies.
- some implementations may include nuclear reactors that employ uranium oxides, uranium hydrides, uranium nitrides, uranium carbides, mixed oxides, and/or other types of radioactive fuel.
- embodiments are not limited to any particular type of reactor cooling mechanism, nor to any particular type of fuel employed to produce heat within or associated with a nuclear reaction.
- FIG. 1 is a diagram of a nuclear reactor module employing a steam generator according to an example embodiment.
- reactor core 5 is positioned at a bottom portion of a cylinder-shaped or capsule-shaped reactor vessel 20.
- Reactor core 5 comprises a quantity of fissile material that generates a controlled reaction that may occur over a period of, for example, several years.
- control rods may be employed to control the rate of fission within reactor core 5.
- Control rods may comprise silver, indium, cadmium, boron, cobalt, hafnium, dysprosium, gadolinium, samarium, erbium, and europium, or their alloys and compounds. However, these are merely a few of many possible control rod materials.
- a cylinder-shaped or capsule-shaped containment vessel 10 surrounds reactor vessel 20 with the containment vessel being partially or completely submerged within a pool of water or other fluid coolant.
- the volume between reactor vessel 20 and containment vessel 10 may be partially or completely evacuated to reduce heat transfer from reactor vessel 20 to the external environment.
- the volume between reactor vessel 20 and containment vessel 10 may be at least partially filled with a gas and/or a fluid that increases heat transfer between the reactor vessel and the containment vessel.
- reactor core 5 may be partially or completely submerged within a fluid, such as water, for example, which may include boron or other additive, which rises after making contact with a surface of the reactor core.
- a fluid such as water, for example, which may include boron or other additive, which rises after making contact with a surface of the reactor core.
- the upward motion of heated coolant is represented by arrow 15 above reactor core 5.
- the coolant travels upward through riser column 30, which may be at least partially or approximately cylinder shaped, and over the top of steam generators 40 and 42 and is pulled downward by way of convection along the inner walls of reactor vessel 20, thus allowing the coolant to impart heat to steam generators 40 and 42.
- contact with reactor core 5 results in heating the coolant as symbolized by arrow 15.
- steam generators 40 and 42 are shown as comprising distinct elements in Figure 1
- steam generators 40 and 42 may represent a number of helical coils that wrap around riser column 30, which may comprise a cylindrical shape.
- another number of helical coils may wrap around an upper portion of riser column 30 in an opposite direction, in which, for example, a first helical coil wraps in a counterclockwise direction, while a second helical coil wraps in a clockwise direction.
- fluid line 70 is shown as being positioned just above upper portions of steam generators 40 and 42, in other implementations, reactor vessel 20 may include a lesser or a greater amount of coolant.
- vaporized coolant is routed from a top portion of heat exchangers 40 and 42 to drive one or more of turbines 80 and 82 that convert the thermal potential energy of steam into electrical energy. After condensing, coolant is returned to a bottom portion of heat exchangers 40 and 42.
- Plenums 85 are located at input ports of steam generators 40 and 42 of Figure 1 .
- plenums 85 include an approximately flat tubesheet that couples coolant from turbines 80/82 to steam generators 40/42.
- At least one of plenums 85 which may be located proximate with a first horizontal plane that intersects a lower portion of riser column 30, comprises an approximately flat tubesheet wherein the flat tubesheet faces upward in the direction of a plane intersecting an upper portion of riser column 30.
- At least one of plenums 87 which may be located proximate with a second horizontal plane intersecting an upper portion of riser column 30, comprises an approximately flat tubesheet wherein the flat tubesheet faces in the direction of a lower portion of the plane intersecting riser column 30.
- Figure 2 shows a dimetric view of a steam generator around an approximately cylindrical riser column according to an example embodiment.
- a flowpath comprising several layers of closely spaced tubes can be seen as extending helically between plenums 100 and plenums 120.
- plenums 100 are spaced at 90-degree intervals in a first plane, such as plane 105, around an approximately cylindrical shape that surrounds a riser column.
- Both plenums 100 and plenums 120 include an approximately flat tubesheet that faces in the direction of plane 115, which intersects a midsection of steam generator 110.
- the tubes extending between plenums 100 and 120 may comprise lengths of approximately 24.0 to 30.0 meters.
- the use of three or more plenums proximate with plane 105 and three or more plenums proximate with plane 125 may result, at least in part, in reducing variation in length to a predetermined threshold of each of the steam generator tubes that forms a flowpath between one of plenums 120 with one or more of plenums 100, for example.
- steam-generator tubes forming one more flowpaths between plenums 100 and 120 might comprise lengths of less than 24.0 meters, such as 22.0 meters, 20.0 meters, 18.0 meters, and other example lengths.
- the tubes extending between plenums 100 and 120 comprise lengths greater than 30.0 meters, such as 32.0 meters, 35.0 meters, 40.0 meters, and other example lengths.
- Plenums 120 which may be approximately located in plane 125 near a bottom portion of a riser column, may also be spaced at 90-degree intervals.
- both plenums 100 and 120 comprise approximately flat tubesheets, wherein each tubesheet comprises perforations for coupling coolant from a plenum to the tubes of steam generator 110.
- each of plenums 100 which may be proximate with plane 105, is shown as being approximately or directly above a corresponding plenum of plenums 120 proximate with plane 125. However, nothing prevents one or more of plenums 100 from being rotated in plane 105 with respect to plenums 120.
- tubesheets include perforations having a diameter of between 15.0 and 20.0 mm for coupling to the tubes of steam generator 110.
- tubesheets may make use of a tubesheet having perforations of less than 15.0 mm, such as 12.0 mm, 10.0 mm in diameter or smaller.
- certain other examples may make use of a tubesheet having perforations greater than 20.0 mm in diameter, such as 25.0 mm, 30.0 mm, 35.0 mm, and other example diameters.
- Figure 3 shows a bottom view of a steam generator around an approximately cylindrical riser column according to an example embodiment.
- plenums 220 may be spaced at approximately 90-degree intervals, for example, around an approximately circular shape, which may represent, for example, riser column 30 of Figure 1 .
- Figure 3 also shows various concentric layers of steam generator tubes, which may surround a riser column.
- Figure 4 shows a top view of a plenum used in a steam generator for a nuclear reactor according to the invention.
- an approximately flat tubesheet having perforations suitable for coupling to individual tubes of a steam generator is shown.
- the perforations of Figure 4 may be arranged in concentric arcs in which a larger number of perforations per unit area (e.g., higher density) may be present towards an outer edge, such as outer edge 260, than at inner edge 250 (e.g., lower density).
- edge 250 may correspond to a portion of the plenum closer to a cylindrical riser column
- outer edge 260 may correspond to a portion of the plenum closer to a wall of a reactor vessel, such as reactor vessel 20 of Figure 1 .
- Figure 5 shows details of a plenum used in a steam generator for a nuclear reactor according to the invention.
- tubesheet 330 is shown as being approximately flat and comprising an increasing density of perforations as the distance from riser column edge 335 increases.
- a much larger density of perforations may be present than at a portion of the tubesheet closer to riser column edge 335.
- Figure 6 shows an orifice used in a tubesheet perforation of a plenum used in a steam generator of a nuclear reactor according to another embodiment of the invention.
- an orifice may be used to reduce pressure of coolant 350, for example, perhaps by an amount of at least 15.0% of an overall pressure drop brought about by the length of a steam generator tube.
- pressure stability which may be of particular concern during startup conditions, for example, may be enhanced.
- a method of operating a nuclear reactor includes conveying a working fluid from a first group of three or more plenums perhaps proximately located, for example, in a first plane of a reactor vessel, to a plurality of flowpaths.
- the conveying includes reducing pressure of the working fluid by an amount sufficient to preclude flow instability.
- the percentage of pressure drop comprises at least 15.0% of an overall pressure drop brought about by a length of steam generator tubing that extends between a first plenum located at a first plane and a second plenum located at a second plane.
- the conveying includes coupling the working fluid to flowpaths through an approximately flat tubesheet of at least one plenum of the first group of three or more plenums.
- the method further includes vaporizing the working fluid in at least some of the plurality of flowpaths, wherein the vaporizing results, at least in part, from coupling thermal energy from a reactor coolant to at least some of the flowpaths.
- the method further includes transferring the vaporizing coolant to a second group of three or more plenums perhaps through an approximately flat tubesheet of at least one of the plenums.
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Plasma & Fusion (AREA)
- Sustainable Energy (AREA)
- Thermal Sciences (AREA)
- Mechanical Engineering (AREA)
- Sustainable Development (AREA)
- Life Sciences & Earth Sciences (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Claims (15)
- Ein Dampferzeuger für einen Kernreaktor, aufweisend einen Reaktorbehälter (20), der eine Säule (30) umschließt, der Folgendes beinhaltet:drei oder mehr Plenen (120) nahe einer ersten Ebene (125), wobei die erste Ebene (125) einen unteren Abschnitt der Säule (30) kreuzt;drei oder mehr Plenen (100) nahe einer zweiten Ebene (105), wobei die zweite Ebene (105) annähernd parallel zur ersten Ebene (125) ist und einen oberen Abschnitt der Säule kreuzt; undeine Vielzahl von dampferzeugenden Rohren, die eine Kühlmittelströmungsweg von einem der drei oder mehr, nahe der ersten Ebene liegenden Plenen (120) bis zu mindestens einem der drei oder mehr Plenen (100) nahe der zweiten Ebene bildet;wobei mindestens eines der drei oder mehr Plenen (120) nahe der ersten Ebene oder mindestens eines der drei oder mehr Plenen (100) nahe der zweiten Ebene eine annähernd flache Rohrplatte (330), die in Richtung eines mittleren Abschnitts der Säule zeigt, umfasst; undwobei die annähernd flache Rohrplatte (330) eine Innenkante (250) und eine Außenkante (260) umfasst, wobei die Innenkante (250) näher an der Säule (30) als die Außenkante (260) positioniert ist, wobei die Außenkante (260) näher an dem Reaktorbehälter (20) als die Innenkante (250) positioniert ist und wobei die annähernd flache Rohrplatte ferner eine Vielzahl von Perforationen umfasst, dadurch gekennzeichnet, dass die Perforationen unweit der Innenkante (250) eine niedrigere Dichte als unweit der Außenkante (260) aufweisen.
- Kernreaktordampferzeuger gemäß Anspruch 1, wobei die drei oder mehr Plenen vier Plenen (120) nahe der ersten Ebene beinhalten, die in Abständen von annähernd 90° um die Säule herum ausgerichtet sind.
- Kernreaktordampferzeuger gemäß Anspruch 1, wobei die drei oder mehr Plenen vier Plenen (100) nahe der zweiten Ebene beinhalten, die in Abständen von annähernd 90° um die Säule herum ausgerichtet sind.
- Kernreaktordampferzeuger gemäß Anspruch 3, wobei jedes der vier Plenen (120) nahe der ersten Ebene direkt unter einem entsprechenden der vier Plenen (100) nahe der zweiten Ebene liegt.
- Kernreaktordampferzeuger gemäß Anspruch 1, wobei die Säule einer Steigleitung entspricht, die einen annähernd kreisförmigen Querschnitt beinhaltet.
- Kernreaktordampferzeuger gemäß Anspruch 1, wobei mindestens einige der Vielzahl von Perforationen eine Öffnung zum Verringern von Druck an einem Einlass eines dampferzeugenden Rohres umfassen.
- Kernreaktordampferzeuger gemäß Anspruch 6, wobei die Öffnung, die mit den mindestens einigen der Vielzahl von Perforationen umfasst ist, einen Druckabfall von mindestens 15,0 % eines Gesamtdruckabfalls einführt, der durch eine Länge eines Dampferzeugerrohres herbeigeführt wird, das sich zwischen einem ersten, in der ersten Ebene liegenden Plenum und einem zweiten, in der zweiten Ebene liegenden Plenum erstreckt.
- Kernreaktordampferzeuger gemäß Anspruch 1, wobei bestimmte der Vielzahl von dampferzeugenden Rohren mit bestimmten anderen der Vielzahl von dampferzeugenden Rohren ineinander verschachtelt sind.
- Kernreaktordampferzeuger gemäß Anspruch 1, wobei sich die Dichte der Perforationen von einer kleineren Anzahl unweit der Innenkante (250) zu einer größeren Anzahl unweit der Außenkante (260) verändert.
- Kernreaktordampferzeuger gemäß Anspruch 1, wobei die Vielzahl von Perforationen in einer Vielzahl von konzentrischen Bögen angeordnet ist.
- Kernreaktordampferzeuger gemäß Anspruch 1, wobei jede Perforation der Vielzahl von Perforationen einen Durchmesser zwischen 15,0 und 20,0 mm aufweist.
- Ein Verfahren zum Betreiben des Kernreaktors gemäß Anspruch 1, wobei das Verfahren Folgendes beinhaltet:Befördern eines Arbeitsfluids von einer ersten Gruppe von drei oder mehr Plenen (120) zu einer Vielzahl von Strömungswegen, wobei mindestens eines der Plenen eine annähernd flache Rohrplatte mit einer Vielzahl von Perforationen aufweist, wobei sich eine Anzahl der Vielzahl von Perforationen pro Flächeneinheit der annähernd flachen Rohrplatte zwischen einer Fläche der annähernd flachen Rohrplatte unweit einer Innenkante des mindestens einen Plenums und einer Fläche unweit einer Außenkante des mindestens einen Plenums verändert, wobei das Befördern ferner das Befördern des Arbeitsfluids zu der Vielzahl von Strömungswegen durch die Vielzahl von Perforationen hindurch beinhaltet;Verdampfen des Arbeitsfluids in mindestens einigen der Vielzahl von Strömungswegen, wobei das Verdampfen zumindest teilweise aus dem Koppeln von Wärmeenergie aus einem Reaktorkühlmittel an die mindestens einigen der Vielzahl von Strömungswegen resultiert; undÜbertragen des verdampften Kühlmittels an eine zweite Gruppe von drei oder mehr Plenen (100).
- Verfahren gemäß Anspruch 12, wobei das Befördern ferner das Verringern des Drucks des Arbeitsfluids beinhaltet.
- Verfahren gemäß Anspruch 13, wobei der Druck des Arbeitsfluids um eine Menge von mindestens 15,0 % eines Gesamtdruckabfalls verringert wird, was zumindest teilweise aus einem Strömungsweg, die sich zwischen einem ersten Plenum der ersten, in einer ersten Ebene liegenden Gruppe von Plenen und einem zweiten Plenum der zweiten, in einer zweiten Ebene liegenden Gruppe von Plenen erstreckt, resultiert.
- Verfahren gemäß Anspruch 12, wobei sich die Strömungswege zwischen der ersten Gruppe von Plenen und der zweiten Gruppe von Plenen spiralförmig erstrecken.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
PL13777696T PL2859556T3 (pl) | 2012-04-20 | 2013-04-19 | Generator pary wodnej dla reaktora jądrowego |
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US13/451,759 US9230697B2 (en) | 2012-04-20 | 2012-04-20 | Steam generator for a nuclear reactor |
PCT/US2013/037292 WO2013158950A2 (en) | 2012-04-20 | 2013-04-19 | Steam generator for a nuclear reactor |
Publications (3)
Publication Number | Publication Date |
---|---|
EP2859556A2 EP2859556A2 (de) | 2015-04-15 |
EP2859556A4 EP2859556A4 (de) | 2016-04-06 |
EP2859556B1 true EP2859556B1 (de) | 2020-12-16 |
Family
ID=49380114
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP13777696.9A Active EP2859556B1 (de) | 2012-04-20 | 2013-04-19 | Dampferzeuger für einen kernreaktor |
Country Status (9)
Country | Link |
---|---|
US (2) | US9230697B2 (de) |
EP (1) | EP2859556B1 (de) |
JP (5) | JP2015514995A (de) |
KR (2) | KR102159794B1 (de) |
CN (1) | CN104272397B (de) |
CA (2) | CA2869901C (de) |
HK (1) | HK1202344A1 (de) |
PL (1) | PL2859556T3 (de) |
WO (1) | WO2013158950A2 (de) |
Families Citing this family (12)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US9230697B2 (en) | 2012-04-20 | 2016-01-05 | Nuscale Power, Llc | Steam generator for a nuclear reactor |
US9997262B2 (en) | 2013-12-26 | 2018-06-12 | Nuscale Power, Llc | Integral reactor pressure vessel tube sheet |
US9897308B2 (en) | 2013-12-26 | 2018-02-20 | Nuscale Power, Llc | Steam generator with tube aligning orifice |
GB2522881B (en) * | 2014-02-07 | 2018-05-09 | Rolls Royce Power Eng Plc | Steam generator |
US10629312B2 (en) * | 2014-12-23 | 2020-04-21 | Nuscale Power, Llc | Light water reactor with condensing steam generator |
US10685752B2 (en) * | 2015-02-10 | 2020-06-16 | Nuscale Power, Llc | Steam generator with inclined tube sheet |
US20170023305A1 (en) * | 2015-07-22 | 2017-01-26 | General Electric Company | Steam generator having an integrated modular heat exchanger |
CN107785084B (zh) * | 2017-07-31 | 2023-10-27 | 清华大学天津高端装备研究院 | 一种自加压型的一体化冷容器型反应堆 |
US10755826B2 (en) | 2017-11-10 | 2020-08-25 | Nugen, Llc | Integrated system for converting nuclear energy into electrical, rotational, and thermal energy |
RU2725161C1 (ru) * | 2019-11-29 | 2020-06-30 | федеральное государственное бюджетное образовательное учреждение высшего образования "Национальный исследовательский университет "МЭИ" (ФГБОУ ВО "НИУ "МЭИ") | Охлаждаемая стенка токамака |
JP7321953B2 (ja) | 2020-02-17 | 2023-08-07 | 株式会社神戸製鋼所 | 自動溶接システム、溶接方法、学習装置、学習済みモデルの生成方法、学習済みモデル、推定装置、推定方法、及びプログラム |
US11421589B1 (en) | 2021-05-18 | 2022-08-23 | Nugen, Llc | Integrated system for converting nuclear energy into electrical, mechanical, and thermal energy |
Family Cites Families (23)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
BE786097A (fr) * | 1971-07-14 | 1973-01-10 | Babcock & Wilcox Co | Perfectionnements aux generateurs de vapeur du type nucleaire |
US3941187A (en) | 1971-07-14 | 1976-03-02 | The Babcock & Wilcox Company | Consolidated nuclear steam generator |
US4174123A (en) * | 1971-07-14 | 1979-11-13 | The Babcock & Wilcox Company | Vessel penetration apparatus |
JPS5723761Y2 (de) * | 1972-10-16 | 1982-05-24 | ||
ZA74176B (en) * | 1973-01-29 | 1974-12-24 | Babcock & Wilcox Co | Consolidated nuclear steam generator |
JPS5127801A (ja) | 1974-08-06 | 1976-03-09 | Kubota Ltd | Sakushonhetsudo |
CA1122202A (en) * | 1979-11-23 | 1982-04-20 | Gordon M. Cameron | Heat exchanger having improved tube layout |
JPS62163994A (ja) * | 1986-01-14 | 1987-07-20 | 株式会社東芝 | 高速増殖炉 |
US5263067A (en) * | 1992-06-24 | 1993-11-16 | Westinghouse Electric Corp. | Locating hot and cold-legs in a nuclear powered steam generation system |
JP3511531B2 (ja) * | 1994-12-14 | 2004-03-29 | 株式会社東芝 | 蒸気発生器 |
JP2000346306A (ja) * | 1999-06-03 | 2000-12-15 | Ishikawajima Harima Heavy Ind Co Ltd | 蒸気発生器の給水入口部 |
JP4101422B2 (ja) | 1999-12-28 | 2008-06-18 | 株式会社東芝 | 液体金属冷却型原子炉および液体金属冷却型原子力プラント |
JP3524884B2 (ja) * | 2001-03-02 | 2004-05-10 | 三菱重工業株式会社 | 高速増殖炉 |
US6813328B2 (en) | 2002-12-13 | 2004-11-02 | Curtiss-Wright Electro-Mechanical Corporation | Nuclear reactor submerged high temperature spool pump |
JP2006162339A (ja) * | 2004-12-03 | 2006-06-22 | Mitsubishi Heavy Ind Ltd | 熱交換器及び原子炉 |
CN101307897B (zh) * | 2008-06-24 | 2010-06-23 | 清华大学 | 保证气冷堆一回路介质在蒸汽发生器内流动均匀性的装置 |
US8971477B2 (en) * | 2009-06-10 | 2015-03-03 | Babcock & Wilcox Mpower, Inc. | Integral helical coil pressurized water nuclear reactor |
JP5127801B2 (ja) | 2009-09-30 | 2013-01-23 | 株式会社藤商事 | 遊技機 |
KR20120132493A (ko) | 2010-02-05 | 2012-12-05 | 에스엠알, 엘엘씨 | 1차 냉각재의 자연순환을 가지는 원자로 시스템 |
EP2561513B1 (de) * | 2010-04-23 | 2019-04-10 | Atomic Energy of Canada Limited | Druckrohrreaktor mit kühlmittelfüllraum |
CA2796487C (en) * | 2010-04-23 | 2021-06-08 | Atomic Energy Of Canada Limited/Energie Atomique Du Canada Limitee | Pressure-tube reactor with pressurised moderator |
US9343187B2 (en) | 2010-09-27 | 2016-05-17 | Bwxt Nuclear Energy, Inc. | Compact nuclear reactor with integral steam generator |
US9230697B2 (en) | 2012-04-20 | 2016-01-05 | Nuscale Power, Llc | Steam generator for a nuclear reactor |
-
2012
- 2012-04-20 US US13/451,759 patent/US9230697B2/en active Active
-
2013
- 2013-04-19 CA CA2869901A patent/CA2869901C/en active Active
- 2013-04-19 WO PCT/US2013/037292 patent/WO2013158950A2/en active Application Filing
- 2013-04-19 CA CA3178009A patent/CA3178009A1/en active Pending
- 2013-04-19 KR KR1020147031799A patent/KR102159794B1/ko active IP Right Grant
- 2013-04-19 EP EP13777696.9A patent/EP2859556B1/de active Active
- 2013-04-19 KR KR1020207027080A patent/KR102220520B1/ko active IP Right Grant
- 2013-04-19 CN CN201380020902.5A patent/CN104272397B/zh active Active
- 2013-04-19 JP JP2015507202A patent/JP2015514995A/ja active Pending
- 2013-04-19 PL PL13777696T patent/PL2859556T3/pl unknown
-
2014
- 2014-12-11 US US14/567,487 patent/US10147507B2/en active Active
-
2015
- 2015-03-18 HK HK15102785.8A patent/HK1202344A1/xx unknown
-
2018
- 2018-10-11 JP JP2018192459A patent/JP2019032339A/ja active Pending
-
2019
- 2019-10-23 JP JP2019192630A patent/JP6882418B2/ja active Active
-
2021
- 2021-05-06 JP JP2021078628A patent/JP2021119356A/ja active Pending
-
2023
- 2023-01-05 JP JP2023000501A patent/JP7514339B2/ja active Active
Non-Patent Citations (1)
Title |
---|
None * |
Also Published As
Publication number | Publication date |
---|---|
CA3178009A1 (en) | 2013-10-24 |
CN104272397A (zh) | 2015-01-07 |
WO2013158950A3 (en) | 2013-11-14 |
WO2013158950A2 (en) | 2013-10-24 |
PL2859556T3 (pl) | 2021-06-14 |
JP6882418B2 (ja) | 2021-06-02 |
JP7514339B2 (ja) | 2024-07-10 |
CA2869901C (en) | 2023-01-17 |
HK1202344A1 (en) | 2015-09-25 |
KR20150003807A (ko) | 2015-01-09 |
JP2015514995A (ja) | 2015-05-21 |
JP2021119356A (ja) | 2021-08-12 |
EP2859556A4 (de) | 2016-04-06 |
JP2023052220A (ja) | 2023-04-11 |
EP2859556A2 (de) | 2015-04-15 |
JP2019032339A (ja) | 2019-02-28 |
KR102220520B1 (ko) | 2021-02-25 |
KR20200111284A (ko) | 2020-09-28 |
CA2869901A1 (en) | 2013-10-24 |
CN104272397B (zh) | 2016-12-21 |
US20150103967A1 (en) | 2015-04-16 |
KR102159794B1 (ko) | 2020-09-24 |
JP2020024214A (ja) | 2020-02-13 |
US20130279643A1 (en) | 2013-10-24 |
US10147507B2 (en) | 2018-12-04 |
US9230697B2 (en) | 2016-01-05 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
EP2859556B1 (de) | Dampferzeuger für einen kernreaktor | |
JP6349443B2 (ja) | 原子炉に使用される熱除去システム | |
JP2014506998A5 (de) | ||
JP6395802B2 (ja) | 原子炉システムと方法 | |
JP2022552608A (ja) | 液体金属合金の燃料及び/又は減速材を有する原子炉 | |
US10629312B2 (en) | Light water reactor with condensing steam generator | |
KR20220077147A (ko) | 원자로로부터의 열 제거와 같은 열 제거를 위한 히트 파이프 네트워크와, 관련 시스템 및 방법 | |
US8822963B2 (en) | Vapor forming apparatus, system and method for producing vapor from radioactive decay material | |
JP2015108536A (ja) | 燃料集合体および加圧水型原子炉 | |
JP2018004445A (ja) | 高速炉用燃料集合体及びそれを装荷する高速炉の炉心 | |
JP2009052999A (ja) | 原子炉 | |
KR20150005420A (ko) | 가압기 배플 플레이트 및 그를 이용한 가압 경수로 |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
PUAI | Public reference made under article 153(3) epc to a published international application that has entered the european phase |
Free format text: ORIGINAL CODE: 0009012 |
|
17P | Request for examination filed |
Effective date: 20141114 |
|
AK | Designated contracting states |
Kind code of ref document: A2 Designated state(s): AL AT BE BG CH CY CZ DE DK EE ES FI FR GB GR HR HU IE IS IT LI LT LU LV MC MK MT NL NO PL PT RO RS SE SI SK SM TR |
|
AX | Request for extension of the european patent |
Extension state: BA ME |
|
DAX | Request for extension of the european patent (deleted) | ||
A4 | Supplementary search report drawn up and despatched |
Effective date: 20160303 |
|
RIC1 | Information provided on ipc code assigned before grant |
Ipc: G21C 15/00 20060101AFI20160226BHEP Ipc: G21C 1/00 20060101ALI20160226BHEP |
|
17Q | First examination report despatched |
Effective date: 20160329 |
|
STAA | Information on the status of an ep patent application or granted ep patent |
Free format text: STATUS: EXAMINATION IS IN PROGRESS |
|
GRAP | Despatch of communication of intention to grant a patent |
Free format text: ORIGINAL CODE: EPIDOSNIGR1 |
|
STAA | Information on the status of an ep patent application or granted ep patent |
Free format text: STATUS: GRANT OF PATENT IS INTENDED |
|
INTG | Intention to grant announced |
Effective date: 20200626 |
|
GRAS | Grant fee paid |
Free format text: ORIGINAL CODE: EPIDOSNIGR3 |
|
GRAA | (expected) grant |
Free format text: ORIGINAL CODE: 0009210 |
|
STAA | Information on the status of an ep patent application or granted ep patent |
Free format text: STATUS: THE PATENT HAS BEEN GRANTED |
|
AK | Designated contracting states |
Kind code of ref document: B1 Designated state(s): AL AT BE BG CH CY CZ DE DK EE ES FI FR GB GR HR HU IE IS IT LI LT LU LV MC MK MT NL NO PL PT RO RS SE SI SK SM TR |
|
REG | Reference to a national code |
Ref country code: GB Ref legal event code: FG4D |
|
REG | Reference to a national code |
Ref country code: IE Ref legal event code: FG4D |
|
REG | Reference to a national code |
Ref country code: DE Ref legal event code: R096 Ref document number: 602013074755 Country of ref document: DE |
|
REG | Reference to a national code |
Ref country code: AT Ref legal event code: REF Ref document number: 1346313 Country of ref document: AT Kind code of ref document: T Effective date: 20210115 |
|
REG | Reference to a national code |
Ref country code: FI Ref legal event code: FGE |
|
REG | Reference to a national code |
Ref country code: NL Ref legal event code: FP |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: NO Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20210316 Ref country code: RS Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20201216 Ref country code: GR Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20210317 |
|
REG | Reference to a national code |
Ref country code: AT Ref legal event code: MK05 Ref document number: 1346313 Country of ref document: AT Kind code of ref document: T Effective date: 20201216 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: SE Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20201216 Ref country code: LV Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20201216 Ref country code: BG Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20210316 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: HR Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20201216 |
|
REG | Reference to a national code |
Ref country code: LT Ref legal event code: MG9D |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: PT Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20210416 Ref country code: RO Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20201216 Ref country code: SK Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20201216 Ref country code: LT Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20201216 Ref country code: EE Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20201216 Ref country code: SM Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20201216 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: AT Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20201216 |
|
REG | Reference to a national code |
Ref country code: DE Ref legal event code: R097 Ref document number: 602013074755 Country of ref document: DE |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: IS Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20210416 |
|
PLBE | No opposition filed within time limit |
Free format text: ORIGINAL CODE: 0009261 |
|
STAA | Information on the status of an ep patent application or granted ep patent |
Free format text: STATUS: NO OPPOSITION FILED WITHIN TIME LIMIT |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: AL Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20201216 Ref country code: IT Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20201216 |
|
REG | Reference to a national code |
Ref country code: DE Ref legal event code: R119 Ref document number: 602013074755 Country of ref document: DE |
|
26N | No opposition filed |
Effective date: 20210917 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: DK Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20201216 Ref country code: ES Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20201216 Ref country code: MC Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20201216 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: LU Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 20210419 |
|
REG | Reference to a national code |
Ref country code: BE Ref legal event code: MM Effective date: 20210430 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: DE Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 20211103 Ref country code: LI Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 20210430 Ref country code: CH Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 20210430 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: SI Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20201216 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: IE Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 20210419 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: IS Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20210416 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: BE Free format text: LAPSE BECAUSE OF NON-PAYMENT OF DUE FEES Effective date: 20210430 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: HU Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT; INVALID AB INITIO Effective date: 20130419 |
|
P01 | Opt-out of the competence of the unified patent court (upc) registered |
Effective date: 20230512 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: CY Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20201216 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: MK Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20201216 |
|
PGFP | Annual fee paid to national office [announced via postgrant information from national office to epo] |
Ref country code: NL Payment date: 20240425 Year of fee payment: 12 |
|
PG25 | Lapsed in a contracting state [announced via postgrant information from national office to epo] |
Ref country code: TR Free format text: LAPSE BECAUSE OF FAILURE TO SUBMIT A TRANSLATION OF THE DESCRIPTION OR TO PAY THE FEE WITHIN THE PRESCRIBED TIME-LIMIT Effective date: 20201216 |
|
PGFP | Annual fee paid to national office [announced via postgrant information from national office to epo] |
Ref country code: GB Payment date: 20240423 Year of fee payment: 12 |
|
PGFP | Annual fee paid to national office [announced via postgrant information from national office to epo] |
Ref country code: CZ Payment date: 20240410 Year of fee payment: 12 |
|
PGFP | Annual fee paid to national office [announced via postgrant information from national office to epo] |
Ref country code: FR Payment date: 20240430 Year of fee payment: 12 Ref country code: FI Payment date: 20240425 Year of fee payment: 12 |
|
PGFP | Annual fee paid to national office [announced via postgrant information from national office to epo] |
Ref country code: PL Payment date: 20240410 Year of fee payment: 12 |